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Denver, CO|The Westin Denver Downtown
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Latest News
Argonne’s METL gears up to test more sodium fast reactor components
Argonne National Laboratory has successfully swapped out an aging cold trap in the sodium test loop called METL (Mechanisms Engineering Test Loop), the Department of Energy announced April 23. The upgrade is the first of its kind in the United States in more than 30 years, according to the DOE, and will help test components and operations for the sodium-cooled fast reactors being developed now.
Ihor O. Bohachevsky, Ronald N. Kostoff
Fusion Science and Technology | Volume 2 | Number 4 | October 1982 | Pages 687-699
Technical Paper | Blanket Engineering | doi.org/10.13182/FST82-A20807
Articles are hosted by Taylor and Francis Online.
Cyclic thermal loads and stresses in two critical components of fusion reactors, including fusion-fission hybrids, are modeled and calculated. The two critical components are the solid wall adjacent to the fusion plasma (“first wall”) and the fissile fuel elements in the high-power density region of the blanket. These two components exemplify two limiting cases of thermal loading: The first-wall loads are generated by predominantly shallow energy deposition that may be approximated with a flux across the surface and the fuel elements loads are generated by volumetric heating. Two approaches are used to solve the heat conduction equation and to calculate the resulting stresses in terms of system parameters. The first is expansion into Fourier series and determination of periodic solutions; the second is analysis and superposition of single-pulse responses weighted with appropriate time delay and decay factors. Approximate closed-form expression for temperature excursions and thermal stresses are derived; these expressions may be evaluated conveniently and rapidly for comparison of different systems. The results provide a quantitative basis for trade-off studies and comparative assessments of different fusion reactor systems.